Computer Programs
NEA-0897 FISP-6.
last modified: 06-DEC-1990 | catalog | categories | new | search |

NEA-0897 FISP-6.

FISP-6, Fission Products Inventory and Energy Release in Irradiated Fuel

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1. NAME OR DESIGNATION OF PROGRAM:  FISP-6.
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2. COMPUTERS
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Program name Package id Status Status date
FISP-6 NEA-0897/03 Tested 06-DEC-1990

Machines used:

Package ID Orig. computer Test computer
NEA-0897/03 IBM 370 series IBM 3090
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3. DESCRIPTION OF PROGRAM OR FUNCTION

FISP-6 calculates fission product inventory and energy release rates in irradiated fuel using  a point model for irradiation and cooling conditions specified by the user. Its basic data requirements of fission yields, radioactive half-lives, average decay energies, beta and gamma spectra, and capture cross sections are held in permanent data library files.
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4. METHOD OF SOLUTION

FISP-6 uses an analytical solution with linearised build-up and decay chains of the fission products. Using  a particular form of the general solution the code is able to reduce the problems of rounding errors which occur with this type of calculation.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

The present version  of FISP-6 allows for a maximum of 96 decay chains each having up to  20 members (including capture products), and a maximum of 650 linearized decay routes. Cross sections are limited to a maximum of  3 groups for each nuclide while a coarse gamma spectrum may have up  to 12 groups.
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6. TYPICAL RUNNING TIME

Running time depends on the nature of the problem to be solved and the used options. The FISP-6 documentation  lists typical running times for a wide range of available options.
NEA-0897/03
NEA-DB executed the test cases included in this package on an IBM 3090 computer. The following execution times were required: 1s14 (case 1); 1s31 (case 2).
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7. UNUSUAL FEATURES OF THE PROGRAM

In addition to performing the standard decay heat summation calculations, FISP-6 is a valuable tool for analysing decay heat predictions in terms of contributions  from individual nuclides, mass chains, or chemical species. Detailed beta and gamma-ray spectra (the latter broadened to match detector response) may be output in either tabular or graphical form. The results of inventory calculations may be stored and retrieved.
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8. RELATED AND AUXILIARY PROGRAMS

FISP-6 supersedes FISP-5, but retains many features introduced in that version.
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9. STATUS
Package ID Status date Status
NEA-0897/03 06-DEC-1990 Tested at NEADB
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10. REFERENCES:
NEA-0897/03, included references:
- A. Tobias:
  FISP6 - An Enhanced Code for the Evaluation of Fission Product
  Inventories and Decay Heat.
  TPRD/B/0097/N82  (June 1982)
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11. MACHINE REQUIREMENTS:
- main storage: 990K bytes
- system clock.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NEA-0897/03 FORTRAN-IV
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:  OS MVS.
NEA-0897/03
MVS/XA (IBM 3090).
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS

The following system routines are required by FISP-6: DECIN, CLOCK,  ERRSAV, ERRSET, ERRSTR, PLOT, RECT, SYMBOL, NUMBER, LINE, INTERP. Note: some of these subroutines come from the CEGB Plotting Package.
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15. NAME AND ESTABLISHMENT OF AUTHORS

          A. Tobias
          Central Electricity Generating Board
          Technology Planning and Research Division
          Berkeley Nuclear Laboratories
          Berkeley
          Gloucestershire GL13 9PB
          UNITED KINGDOM
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16. MATERIAL AVAILABLE
NEA-0897/03
File name File description Records
NEA0897_03.001 Information file 105
NEA0897_03.002 FISP-6 source program 3587
NEA0897_03.003 RISLEY subroutines (FORTRAN) 1780
NEA0897_03.004 RISLEY subroutines (ASSEMBLER) 614
NEA0897_03.005 Dummy graphic routines 12
NEA0897_03.006 Library converter (for main library) 69
NEA0897_03.007 Library converter (for gamma and beta) 28
NEA0897_03.008 JCL to compile, link and run FISP-6 279
NEA0897_03.009 Input data for test case 1 124
NEA0897_03.010 Input data for test case 2 128
NEA0897_03.011 Gamma-beta library based on UKFPDD2 15546
NEA0897_03.012 Main data library used in testing 1731
NEA0897_03.013 Main data library based on UKFPDD2 14805
NEA0897_03.014 Main data library based on JEF1 14560
NEA0897_03.015 Output for test case 1 822
NEA0897_03.016 Output for test case 2 860
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17. CATEGORIES
  • D. Depletion, Fuel Management, Cost Analysis, and Power Plant Economics

Keywords: decay heat, fission products, inventories, spectra.